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Investigation of gamma-ray shielding capability of glasses doped with Y, Gd, Nd, Pr and Dy rare earth using MCNP-5 code
Physica B xxx (xxxx) xxx
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Investigation of gamma-ray shielding capability of glasses doped with Y, Gd, Nd, Pr and Dy rare earth using MCNP-5 code K.M. Mahmoud a, b, Y.S. Rammah c, * a
Ural Federal University, St. Mira, 19, 620002, Yekaterinburg, Russia Nuclear Materials Authority, Maadi, Cairo, Egypt c Physics Department, Faculty of Science, Menoufia University, Shebin El-Koom, 32511, Menoufia, Egypt b
A R T I C L E I N F O
A B S T R A C T
Keywords: REE MAC MFP HVL Zeff Aeff
The capability of using five rare earth oxides (Y2O3 (S1-Y), Gd2O3 (S2-Gd), NdCl3 (S3-Nd), PrO11 (S4-Pr), and Dy2O3 (S5-Dy)) doped glasses as gamma-rays shielding has been evaluated. The mass attenuation coefficient (MAC, μm) in the photon energy between 0.015 and 15 MeV has been simulated with help of MCNP5- code and calculated by XCOM program. There was agreement between the calculated and simulated results. The highest μm was found for the glass samples S4-Pr, S5-Dy and S3-Nd, respectively while, the lowest μm obtained for Yttrium glass sample (S1-Y). Several another γ-rays shielding parameters such as mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and effective electron density (Aeff) for the studied glasses have been evaluated and compared with some commercial radiation shielding materials such as concretes, heavy metal oxides, and RS-520 glass. Results reveal that the lowest HVL obtained for the samples (S4-Pr and S5-Dy), while the highest HVL obtained for S1-Y sample. The highest Zeff is obtained for S4-Pr glass sample, while the lowest Zeff is obtained by S1-Y. generally, the rare earth glass samples (S4-Pr and S5-Dy) have good shielding properties corresponding to commercially standard RS-520 (SF6), Zinc bismuth borate glass (10ZnO-30Bi2O360B2O3) and concretes.
1. Introduction In our life, humans, animals, and plants can be exposed to several different types of radiations such as neutron, γ/X rays. These radiations are used in different fields like medical therapy, elemental analysis, and nuclear reactors [1]. Gamma-rays (γ-photons) characterized with no charge and mass, therefore, these photons can easily travel for very long distance in air and highly penetrate through materials. For these reasons, γ-photons are difficult to shield. In the other hand, the exposure to gamma radiation for long times may cause damage at a cellular level and are penetrating causing diffuse damage throughout the body leads to genetic damage, cancer and death. So, investigators and researchers have paid efforts to choose and develop new radiation shielding materials to protect humans from the harmful γ-photons [2–13]. To achieve this purpose, the study of radiation interaction mechanism with materials is necessary for evalu ating the level of penetration of radiation in the medium. Therefore, these knowledges have a great importance in the fields of science, in dustrial, and technology. Recently, γ-rays spectrometry techniques find
wide applications in several areas like (i) agriculture to estimate the properties of irradiation of seeds and soil samples, (ii) medical appli cations includes nuclear medicine, radiotherapy, and computerized to mography, and (iii) industry area to detect blockages in underground pipes, to control and measure the flow of liquids, and to examine defects in metal castings [14–17]. The evaluation of a radiation shielding ma terial requires accurate determination of some shielding parameters such as photon attenuation coefficient, effective atomic number, elec tron density, mean free path and half value thickness. Various materials such as alloys, polymers, concretes, glasses, ceramics, bricks, and clay materials have been considered as suitable γ-radiation shielding competence [18–23]. Nowadays, glasses have considered as promising materials for γ-photons shielding due to their high optical transparency and easy to form. Recently, Borate glasses have been prepared and investigated in wide range due to their good thermal stability, low vis cosity, high chemical resistance, low melting point, and excellent me chanical stability [6–10]. Rare earth doped glasses showed a development on the optical properties, density of the produced glasses [24–26]. Furthermore, they
* Corresponding author. E-mail address: [email protected] (Y.S. Rammah). https://doi.org/10.1016/j.physb.2019.411756 Received 16 August 2019; Received in revised form 3 October 2019; Accepted 5 October 2019 Available online 10 October 2019 0921-4526/© 2019 Elsevier B.V. All rights reserved.
Please cite this article as: K.M. Mahmoud, Y.S. Rammah, Physica B, https://doi.org/10.1016/j.physb.2019.411756
K.M. Mahmoud and Y.S. Rammah
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
22.6MgO-20.15CaO-2.52BaO-2.52ZnO-47.85SiO2-1.79B2O3-1.26A l2O3-1.26Gd2O3 (S2-Gd) [30], 65B2O3-12.5TeO2-12.5Bi2O3-5 Na2O-5NdCl3 (S3-Nd) [31], 67TeO2-20WO3-10Li2O-3PrO11 (S4-Pr) [32], and 60B2O3-20BaO-17.5Bi2O3-2.5Dy2O3 (S5-Dy) [33]. The chemical composition and density of the chosen glasses haven been listed in Table 1.
Table 1 Chemical composition and density of the selected rare earth doped glasses. Sample code
Chemical composition
Density, (g/ cm3)
Ref.
S1-Y S2-Gd
35.7Na2O-57.1B2O3-7.2Y2O3 22.6MgO-20.15CaO-2.52BaO-2.52ZnO47.85SiO2-1.79B2O3-1.26Al2O3-1.26Gd2O3 65B2O3-12.5TeO2-12.5Bi2O3-5Na2O-5NdCl3 67TeO2-20WO3-10Li2O-3PrO11 60B2O3-20BaO-17.5Bi2O3-2.5Dy2O3
2.53 3.09
[29] [30]
3.82 5.89 6.70
[31] [32] [33]
S3-Nd S4-Pr S5-Dy
2.2. Methods 2.2.1. Theoretical background Beer Lambert’s law has been used to describe the attenuation process of gamma photons as [16]:
showed a good sensitivity for absorbing UV–visible radiations and emitting visible radiations that may make it as a promising candidate for sensing electromagnetic radiations [27]. Recently, Er2O3 content found to increase the shielding properties of glass (i.e. increase of the mass attenuation coefficient μm; decrease of the half value layer HVL and exposure buildup factor EBF) [28]. In the present work, some glass systems include rare earth oxides such as Y2O3 (Yttrium oxide), Gd2O3 (Gadolinium oxide), NdCl3 (Neo dymium oxide), PrO11 (praseodymium oxide), and Dy2O3 (dysprosium oxide) have been chosen. The capability to use these systems as gamma radiation shielding has been evaluated via calculating the mass atten uation coefficient (MAC, μm) in the photon energy between 0.015 and 15 MeV. Based the values μm, several gamma-ray shielding parameters such as mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and effective electron density for the selected rare earth glasses have been evaluated and compared with some commercial shielding materials (concretes, zinc bismuth borate glass, and RS-520 glass).
I ¼ Io e
(1)
μy
Io and I represent to the intensity of the incident and transmittance photon beam, y is the absorber (the glass sample) thickness, and μ is the linear attenuation coefficient (LAC). The LAC gives the probability of photon interaction per unit length and expressed in cm 1. The mass attenuation coefficient (MAC, μm) of the absorber is calculated from μ values divided by the absorber density and expressed in cm2/g. The MAC (μ/ρ) is used to describe the γ-ray penetration and interaction with the materials and theoretically can be calculated using the mixture rule [6]. μ X �μ� MAC ¼ μm ¼ ¼ Wi (2)
ρ
i
ρ
i
2. Materials and methods
where (μ/ρ)i is the mass attenuation coefficient of the ith constituent element and wi is the weight fraction of the ith constituent element in the glass sample. The half value layer (HVL) and mean free path (MFP) for the shielding material are given by Ref. [15].
2.1. Materials
HVL ¼
The studied glass samples in the present wok have been selected from earlier reports as 35.7Na2O-57.1B2O3-7.2Y2O3 (S1-Y) [29],
MFP ¼
ln 2
(3)
μ 1
(4)
μ
The effective atomic number (Zeff) for the glass sample can be Table 2 The mass attenuation coefficient of the prepared glass samples. Energy (MeV)
Mass attenuation coefficient (cm2/g) S1-Y
0,015 0,02 0,03 0,04 0,05 0,06 0,08 0,1 0,15 0,2 0,3 0,4 0,5 0,6 0,8 1 1,5 2 3 4 5 6 8 10 15
S2-Gd
S3-Nd
S4-Pr
S5-Dy
MCNP
XCOM
MCNP
XCOM
MCNP
XCOM
MCNP
XCOM
MCNP
XCOM
3,5291 4,6686 1,9241 0,9521 0,5378 0,3819 0,2490 0,1957 0,1458 0,1260 0,1056 0,0935 0,0850 0,0784 0,0687 0,0616 0,0501 0,0432 0,0350 0,0304 0,0274 0,0254 0,0228 0,0213 0,0195
3,5400 4,9190 1,7380 0,8700 0,5374 0,3817 0,2489 0,1957 0,1460 0,1261 0,1057 0,0936 0,0851 0,0785 0,0688 0,0618 0,0503 0,0433 0,0351 0,0305 0,0275 0,0255 0,0229 0,0213 0,0195
12,4490 5,5636 1,8411 1,3729 0,8905 0,8027 0,3721 0,2640 0,1701 0,1385 0,1112 0,0972 0,0878 0,0807 0,0705 0,0631 0,0513 0,0444 0,0364 0,0320 0,0292 0,0274 0,0252 0,0240 0,0228
12,4200 5,5490 1,8380 1,3430 0,7973 0,6429 0,3709 0,2634 0,1701 0,1384 0,1112 0,0972 0,0879 0,0808 0,0706 0,0633 0,0515 0,0445 0,0365 0,0320 0,0293 0,0274 0,0252 0,0240 0,0228
21,9099 14,1212 4,9710 4,1052 3,1213 2,1522 1,0246 1,2891 0,4884 0,2777 0,1487 0,1132 0,0955 0,0846 0,0711 0,0621 0,0499 0,0433 0,0360 0,0322 0,0298 0,0284 0,0267 0,0260 0,0257
21,9200 14,1700 4,9880 4,1110 2,7230 1,7320 0,8732 1,0160 0,4269 0,2559 0,1491 0,1135 0,0957 0,0848 0,0713 0,0628 0,0503 0,0435 0,0361 0,0323 0,0299 0,0284 0,0268 0,0261 0,0257
50,5627 23,6228 8,0081 12,2029 7,8070 5,6743 3,5983 2,2196 0,7235 0,3744 0,1785 0,1217 0,0979 0,0843 0,0843 0,0587 0,0470 0,0415 0,0363 0,0343 0,0335 0,0333 0,0337 0,0346 0,0373
50,7000 23,6600 8,0850 12,9000 7,3500 4,5470 3,0920 1,7470 0,6497 0,3497 0,1747 0,1221 0,0982 0,0846 0,0690 0,0599 0,0476 0,0418 0,0366 0,0344 0,0336 0,0333 0,0337 0,0346 0,0373
32,5242 20,6714 7,2467 6,9615 4,1101 3,1452 1,5685 1,6946 0,6540 0,3586 0,1779 0,1276 0,1008 0,0876 0,0722 0,0622 0,0497 0,0432 0,0365 0,0332 0,0313 0,0301 0,0291 0,0288 0,0294
32,5400 20,7400 7,2650 7,0660 4,0060 2,7120 1,3290 1,4590 0,5767 0,3245 0,1718 0,1237 0,1011 0,0879 0,0724 0,0631 0,0501 0,0435 0,0367 0,0333 0,0314 0,0302 0,0291 0,0289 0,0294
2
K.M. Mahmoud and Y.S. Rammah
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
Fig. 1. The variation of the mass attenuation coefficient with the incident gamma ray energy for [A] Yttrium glass, [B] Gadolinium glass, [C] Neodymium glass, [D] presidium glass and [E] Dysprosium glass.
Fig. 2. The variation of MFP of the prepared concrete with the incident gamma ray energy.
calculated using the following relations �� P μ i fi Ai ρ Zeff ¼ P � � i Aj μ j Zj
ρ
Fig. 3. The Variation of HVL with the incident gamma ray energy.
Where NA is Avogardo’s number and M is the atomic mass of the glass. 2.2.2. MNCP-5 simulation code In the currently work, the μ/ρ has been simulated for the chosen glasses using Monte Carlo N particle transport code MCNP- 5 code [34]. This code used to model the interaction of neutrons, gamma-rays, X-rays, and electrons with different materials. In the simulation pro cess, MCNP- 5 code needs an input file includes all data about elemental composition, density, and geometry specification of the proposed ma terial, source specification and tally, more description in Ref. [23].
(5)
j
Where fi Ai and Zj refers to the fractional abundance, atomic weight and atomic number of the ith constituent element respectively. Additionally, the effective electron density (Neff) can be estimated using (Zeff) as: Aeff ¼
X NA ni Zeff M
2.2.3. XCOM program XCOM is a database has been established by Berger and Hubell in
(6)
3
K.M. Mahmoud and Y.S. Rammah
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
Fig. 6. Comparison between the μm of studied samples and some available radiation shielding.
Fig. 4. The variation of the Zeff with the incident energy between 0.01 and 15 MeV.
Fig. 7. Comparison between the HVL of studied samples and some available radiation shielding.
Fig. 5. The variation of the Aeff with the incident energy between 0.01 and 15 MeV.
tends to its maximum value 3.529 cm2/g at low gamma ray energy (for 0.015 MeV) then, it decreases rapidly with the incident energy increase between (0.015 < E < 0.08 MeV) due to the photoelectric cross section which proportional to E 3.5 and Z4 5 [15]. Fig. 1A shows a sudden peak at energy 0.017 MeV due to the K absorption edges of Yttrium. No peaks appear due to Na element because it is occurring only at 0.00107 MeV while we selected the energy range to start from 0.015 MeV. Further increase of the incident gamma ray energy leads to a gradually decrease in the μm between (0.08 < E < 3 MeV) due to the Compton scattering cross section with proportional to the shielding material atomic number [37]. The μm has a slow variation with the incident energy for high incident energy (E > 3 MeV) due to the pair production cross section which proportional to log E [23]. The μm tends to its minimum values 0.0194 cm2/g at high gamma ray energy (for 15 MeV). Fig. 1B reveals that the μm for Gadolinium glass samples (S2-Gd) tends to maximum value 12.449 cm2/g at gamma ray energy 0.015 MeV while the μm tends to minimum values 0.0227 cm2/g at 15 MeV. Fig. 1B illustrates that there are two suddenly peaks at low energy, the first appears at 0.0374 MeV due to K absorption edges of Ba while, the second
1987 to calculate the mass attenuation coefficient of compounds, ele ments, and mixtures in energy range between (1 KeV < E < 1 GeV) [35]. Several researchers have been used the XCOM database to calculate the mass attenuation coefficient for different materials such as polymers, concretes, building materials and glasses [1,10,23,36]. 3. Results and discussion The mass attenuation coefficient μm simulated for five different glass samples prepared with additive of some rare earth elements (Y, Gd, Nd, Pr and Dy) using MCNP-5 code. Furthermore, the μm calculated theo retically for the prepared samples using XCOM data base between 0.015 and 15 MeV as listed in Table 2. It is clear that from Fig. 1 the μm for all prepared glass samples depended on the incident gamma ray energy and the additive materials. Also Fig. 1 reveals that the simulated and calculated are closed together which insure the accuracy of simulation processes. It is clear that from Fig. 1A, the μm of Yttrium glass samples (S1 -Y) 4
K.M. Mahmoud and Y.S. Rammah
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
Table 3 Comparison between the values of the half value layers of the prepared glass samples and other known shielding materials. Energy (MeV) 0,015 0,02 0,03 0,04 0,05 0,06 0,08 0,1 0,15 0,2 0,3 0,4 0,5 0,6 0,8 1 1,5 2 3 4 5 6 8 10 15
Half value layer (cm) S1-Y
S2-Gd
S3-Nd
S4-Pr
S5-Dy
Concrete
Zinc Bismuth borate glass
RS-520 (SF6)
0,078 0,059 0,142 0,288 0,509 0,717 1,100 1,400 1,879 2,174 2,596 2,929 3,223 3,494 3,985 4,446 5,464 6,342 7,821 9,012 9,989 10,798 12,018 12,869 14,082
0,018 0,040 0,122 0,163 0,252 0,279 0,603 0,850 1,318 1,620 2,018 2,308 2,555 2,779 3,180 3,557 4,369 5,055 6,168 7,017 7,679 8,197 8,915 9,358 9,860
0,008 0,012 0,034 0,041 0,054 0,078 0,165 0,131 0,345 0,607 1,134 1,490 1,766 1,994 2,371 2,716 3,379 3,897 4,686 5,246 5,651 5,947 6,310 6,489 6,575
0,002 0,005 0,015 0,010 0,015 0,021 0,033 0,053 0,163 0,314 0,659 0,967 1,202 1,396 1,396 2,005 2,504 2,838 3,238 3,430 3,513 3,539 3,496 3,404 3,156
0,003 0,005 0,014 0,015 0,025 0,033 0,066 0,061 0,158 0,289 0,581 0,811 1,026 1,181 1,433 1,663 2,083 2,393 2,834 3,121 3,310 3,435 3,560 3,592 3,524
0,043 0,097 0,288 0,556 0,841 1,247 1,475 1,747 2,111 2,371 2,774 3,114 3,418 3,770 4,218 4,693 5,764 6,685 8,214 9,430 10,411 11,201 12,369 13,152 14,199
0,004 0,006 0,018 0,039 0,070 0,112 0,224 0,105 0,267 0,482 0,938 1,325 1,635 1,889 2,304 2,648 3,334 3,835 4,550 5,022 5,335 5,544 5,759 5,822 5,726
0,002 0,003 0,008 0,017 0,031 0,050 0,044 0,118 0,231 0,522 0,825 1,094 1,329 1,712 2,026 2,610 2,972 2,996 3,382 3,577 3,658 3,675 3,622 3,520 3,248
appears at 0.0502 MeV due to Gadolinium K-absorption edges. No peaks are found from Al, Si, Ca and Zn elements. Fig. 1C depicts that the highest μm for Neodymium glass samples (S3-Nd) is 21.909 cm2/g and observed at low energy 0.015 MeV while, the lowest μm is 0.0256 cm2/g and observed at 15 MeV. It is clear that there are 3 different peaks in the low gamma ray energy. The peaks appear at 0.0318,0.0436 and 0.0905 due the K-absorption edges of Te, Nd and Bi, respectively. The μm for S3Nd glass tends to minimum value 0.0265 cm2/g at 15 MeV wile, no peaks appear from chlorine. The results illustrated in Fig. 1D, show that the μm of the praseo dymium glass (S4-Pr) tends to a maximum value 50.562 cm2/g at 0.015 MeV, while it tends to a minimum value 0.0373 cm2/g at 15 MeV. Two different peaks appear at 0.0420 and 0.0695 MeV due to the K absorption edges of praseodymium and tungsten, respectively. Fig. 1E reveals that the highest μm for dysprosium glass (S5-Dy) is 32.524 cm2/g and obtained for 0.015 MeV, while the lowest μm is 0.0197 cm2/g and obtained for 15 MeV. It is clear that three different peaks appear at 0.0374, 0.0538 and 0.0905 MeV due to the K absorption edges of Ba, Dy and Bi, respectively [38]. In the present work and according to the previous discussion, it is clear that the highest three μm obtained for S4-Pr, S5-Dy and S3-Nd, respectively, while the lowest μm obtained for Yttrium glass sample (S1-Y). Furthermore, the simulated μm used to calculate other important shielding parameters such as MFP, HVL, Zeff and Aeff that describe the penetration, diffusion, and interaction of the incident gamma ray inside the shielding material. Fig. 2 depicts the variation of the MFP of all prepared glass samples with the incident gamma ray energy between 0.015 and 15 MeV. It is clear that for all REE/glass samples the MFP tends to its minimum values at low energy (for 0.015 MeV) and varied between 0.00335 and 0.112 cm for (S4-Pr and S5-Dy) and S1-Y, respectively. Then, further increases in the incident energy the MFP increase rapidly due to the photoelectric cross section which propor tional to E 3.5. In the intermediate energy range (for 0.1 < E < 3 MeV), the MFP increases gradually with increase the incident energy due to the Compton scattering cross section which depended only atomic number of the shielding material, while there are a slow variation in the MFP for the prepared REE/glass samples at high energy (E > 3 MeV) due to the pair production cross section which proportional to log E. The MFP tends
to maximum values at high energy (for 15 MeV) and it is varied between 4.553 and 20.316 cm for S4-Pr and S1-Y, respectively. The lowest MFP is obtained for samples (S4-Pr and S5-Dy) and varied between 0.00335 and 4.553 cm, while the highest MFP obtained for S1-Y sample and varied between 0.112 and 20.316 in energy range between 0.015 and 15 MeV. Fig. 3 reveals that the dependence of the HVL of the prepared REE/ glass on the incident gamma ray energy which can be described as in the previous section of the MFP. The lowest HVL obtained for the samples (S4-Pr and S5-Dy) and varied between 0.00232 and 3.156 cm at gamma ray energy between 0.015 MeV and 15 MeV. The highest HVL obtained for S1-Y sample and varied between 0.0776 and 14.081 cm. The previous discussion of the μm, HVL and MFP reveals that the glass samples with Pr and Dy (S4-Pr and S5-Dy) have the best shielding parameters, while the sample S1-Y has the lowest shielding properties in the present study. Fig. 4 depicts that the variation of the Zeff of the prepared REE/glass with the incident gamma ray energy between 0.01 and 15 MeV. It is observed that the Zeff for all glass samples tends to maximum values at low energy between 0.02 and 0.04 MeV, while it tends to minimum values at intermediate energy between 1.332 and 1.5 MeV. Fig. 4 reveals that in energy region between 0.01 and 0.3 MeV, the Zeff for all glass samples decreases rapidly with increase of the incident gamma ray en ergy due to the photoelectric cross section. It is also observed that there a suddenly increase in the Zeff at low energy due to the K absorption edges of Y, Gd, Nd, Pr and Dy. Further increases in the incident gamma ray energy, the Zeff decreases gradually due to the Compton scattering cross section. It is also clear that for high energy region (E > 3 MeV), the Zeff increases slowly with the increase of the incident energy due to the pair production cross section. The highest Zeff is obtained for S4-Pr glass sample and varied between 45.610 and 61.634 while, the lowest Zeff is obtained by S1-Y and varied between 10.067 and 33.290. Fig. 5 reveals that the dependence of the Aeff on the incident gamma ray energy. It is clear that, the variation of Aeff with the incident gamma ray energy can be discussed as in the Zeff section. The highest Aeff is obtained for S1-Y and varied between 2.977 � 1023 and 9.85 � 1023 electrons/g while the lowest Aeff is obtained for S4-Pr and varied be tween 2.741 � 1023 and 3.704 � 1023 electrons/g. Fig. 6 reveals that a comparison between the μm for the highest three glass samples in this work (S4-Pr, S5- Dy and S3-Nd) and the μm for some 5
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
K.M. Mahmoud and Y.S. Rammah
available radiation shielding materials such as concrete [39], Zinc bis muth borate glass oxides (10ZnO-30Bi2O3-60B2O3) [40], and Rs-520 (SF6) glass [41]. Fig. 6 displays that, the μm for S4-Pr and S5-Dy higher than the μm for the ordinary concrete and heavy metal oxides but lower than the μm for glass Rs-520 while, glass sample S3-Nd has μm higher than ordinary concrete but lower than the Zinc bismuth borate glass. Fig. 7 and Table 3 showed the comparison between the HVL of our prepared samples and those for some radiation shielding materials. The HVL of our sample S4-Pr equal to the HVL for RS-520 glass while it is higher than the HVL of ordinary concrete and zinc bismuth borate glass. It is also clear that the S5-Dy sample has HVL lower than RS-520, or dinary concrete and heavy metal oxides. Finally, we can conclude that our REE/glass samples (S4-Pr and S5Dy) have good shielding properties corresponding to commercially standard RS-520 (SF6) and available radiation shielding materials namely zinc bismuth borate glass (10ZnO-30Bi2O3-60B2O3) and concretes.
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Tashlykov, Gamma ray shielding characteristics and exposure buildup factor for some natural rocks using MCNP-5 code, Nucl. Eng. Technol. 51 (2019) 1835–1841, https://doi.org/10.1016/j.net.2019.05.013. [16] S.S. Obaid, M.I. Sayyed, D.K. Gaikwad, P.P. Pawar, Attenuation coefficients and exposure buildup factor of some rocks for gamma ray shielding applications, Radiat. Phys. Chem. 148 (2018) 86–94, https://doi.org/10.1016/j. radphyschem.2018.02.026. [17] D.K. Gaikwad, S.S. Obaid, M.I. Sayyed, R.R. Bhosale, V.V. Awasarmol, Ashok Kumar, M.D. Shirsat, P.P. Pawar, Comparative study of gamma ray shielding competence of WO 3 -TeO 2 - PbO glass system to different glasses and concretes, Mater. Chem. Phys. 213 (2018) 508–517, https://doi.org/10.1016/j. matchemphys.2018.04.019. [18] J. Singh, H. Singh, J. Sharma, T. Singh, P.S. Singh, Fusible alloys : a potential candidate for gamma rays shield design, Prog. Nucl. Energy 106 (2018) 387–395, https://doi.org/10.1016/j.pnucene.2018.04.002. [19] V.P. Singh, S.P. Shirmardi, M.E. Medhat, N.M. Badiger, Determination of mass attenuation coefficient for some polymers using Monte Carlo simulation, Vaccum 119 (2015) 284–288, https://doi.org/10.1016/j.vacuum.2015.06.006. [20] A.M. Abu El-soad, M.I. Sayyed, K.A. Mahmoud, S¸. Erdem, E.G. Kovaleva, Simulation Studies for Gamma Ray Shielding Properties of Halloysite Nanotubes Using MCNP-5 Code, vol. 154, 2019, pp. 1–6, https://doi.org/10.1016/j. apradiso.2019.108882. [21] M.I. Sayyed, G. Lakshminarayana, I. V Kityk, M.A. Mahdi, Evaluation of shielding parameters for heavy metal fluoride based tellurite-rich glasses for gamma ray shielding applications, Radiat. Phys. Chem. 139 (2017) 33–39, https://doi.org/ 10.1016/j.radphyschem.2017.05.013. [22] M.I. Sayyed, F. Akman, A. Kumar, M.R. Kaçal, Evaluation of radioprotection properties of some selected ceramic samples, Results Phys. 11 (2018) 1100–1104, https://doi.org/10.1016/j.rinp.2018.11.028. [23] K.A. Mahmoud, M.I. Sayyed, O.L. Tashlykov, Comparative studies between the shielding parameters of concretes with different additive aggregates using MCNP-5 simulation code, Radiat. Phys. Chem. (2019), 108426, https://doi.org/10.1016/j. radphyschem.2019.108426. [24] S. Insitipong, J. Kaewkhao, T. Ratana, P. Limsuwan, Optical and structural investigation of bismuth borate glasses doped with Dy3þ, Procedia Eng. 8 (2011) 195–199, https://doi.org/10.1016/j.proeng.2011.03.036. [25] J. Pisarska, Luminescence behavior of Dy3þ ions in lead borate glasses, Opt. Mater. (Amst). 31 (2009) 1784–1786, https://doi.org/10.1016/j.optmat.2008.11.028. [26] K. Nanda, N. Berwal, R.S. Kundu, R. Punia, N. Kishore, Effect of doping of Nd3þ ions in BaO–TeO2–B2O3 glasses: a vibrational and optical study, J. Mol. Struct. 1088 (2015) 147–154, https://doi.org/10.1016/j.molstruc.2015.02.021. [27] P. Kaur, D. Singh, T. Singh, Optical, photoluminescence and physical properties of Sm3 þ doped lead alumino phosphate glasses, J. Non-Cryst. Solids 452 (2016) 87–92, https://doi.org/10.1016/j.jnoncrysol.2016.08.020. [28] O. Agar, E. Kavaz, E.E. Altunsoy, O. Kilicoglu, H.O. Tekin, M.I. Sayyed, T. T. Erguzel, N. Tarhan, Er2O3 effects on photon and neutron shielding properties of TeO2 -Li2O-ZnO-Nb2O5 glass system, Results Phys. 13 (2019), https://doi.org/ 10.1016/j.rinp.2019.102277. [29] S. Nakayama, T. Watanabe, T. Asahi, H. Kiyono, Y.L. Aung, M. Sakamoto, Influence of rare earth additives and boron component on electrical conductivity of sodium rare earth borate glasses, Ceram. Int. 36 (2010) 2323–2327, https://doi.org/ 10.1016/j.ceramint.2010.07.026. [30] I. Kansal, A. Goel, D.U. Tulyaganov, J.M.F. Ferreira, Effect of some rare-earth oxides on structure, devitrification and properties of diopside based glasses, Ceram. Int. 35 (2009) 3221–3227, https://doi.org/10.1016/j.ceramint.2009.05.023. [31] Y.S. Rammah, A.A. Ali, R. El-Mallawany, A.M. Abdelghany, Optical properties of bismuth borotellurite glasses doped with NdCl3, J. Mol. Struct. 1175 (2019) 504–511, https://doi.org/10.1016/j.molstruc.2018.07.071. [32] S.E. Ibrahim, Y.S. Rammah, I.Z. Hager, R. El-Mallawany, UV and electrical properties of TeO2-WO3-Li2O-Nb2O5/Sm2O3/Pr6O11/Er2O3 glasses, J. Non-
4. Conclusion This work aimed to evaluate the capability of using five rare earth oxides (Y2O3, Gd2O3, NdCl3, PrO11, and Dy2O3) doped glasses as gamma radiation shielding. The mass attenuation coefficient (MAC, μm) in the photon energy between 0.015 and 15 MeV has been simulated using MCNP5- code and calculated by XCOM program. The comparison showed agreement between the calculated and simulated results. Based the μm values, many gamma-rays shielding parameters such as mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and effective electron density for the glasses have been evaluated and compared with some commercial radiation shielding materials such as concretes, zinc bismuth borate glass, and RS-520 glass. Results reveal that: 1 The highest μm was obtained for glass samples S4-Pr, S5-Dy and S3Nd, respectively while, the lowest μm obtained for Yttrium glass sample (S1-Y). 2 The lowest HVL obtained for the samples (S4-Pr and S5-Dy) and varied between 0.00232 and 3.156 cm at gamma ray energy between 0.015 MeV and 15 MeV. The highest HVL obtained for S1-Y sample and varied between 0.0776 and 14.081 cm. 3 The highest Zeff is obtained for S4-Pr glass sample and varied be tween 45.610 and 61.634 while, the lowest Zeff is obtained by S1-Y and varied between 10.067 and 33.290. Finally, one can conclude that our REE/glass samples (S4-Pr and S5Dy) have good shielding properties corresponding to commercially standard RS-520 (SF6), available zinc bismuth borate glass (10ZnO30Bi2O3-60B2O3) and concretes. References [1] K.A. Mahmoud, O.L. Tashlykov, A.F. El Wakil, I.E. El Aassy, Aggregates grain size and press rate dependence of the shielding parameters for some concretes, Prog. Nucl. Energy 118 (2020), 103092, https://doi.org/10.1016/j. pnucene.2019.103092. [2] M.I. Sayyed, K.M. Kaky, D.K. Gaikwad, O. Agar, U.P. Gawai, S.O. Baki, Physical, structural, optical and gamma radiation shielding properties of borate glasses containing heavy metals (Bi2O3/MoO3, J. Non-Cryst. Solids 507 (2019) 30–37. [3] Y.S. Rammah, M.I. Sayyed, A.S. Abohaswa, H.O. Tekin, FTIR, electronic polarizability and shielding parameters of B2O3 glasses doped with SnO2, Appl. Phys. A 124 (2018) 650. [4] A.M.A. Mostafa, S.A.M. Issa, M.I. Sayyed, Gamma ray shielding properties of PbOB2O3 -P2O5 doped with WO3, J. Alloy. Comp. 708 (2017) 294–300. [5] M.I. Sayyed, M.H.M. Zaid, K.A. Matori, Comprehensive study on physical, elastic and shielding properties of ternary BaO-Bi2O3-P2O5 glasses as a potent radiation shielding material, J. Non-Cryst. Solids 468 (2017) 92–99, https://doi.org/ 10.1016/j.jnoncrysol.2017.04.031. [6] Y.S. Rammah, M.I. Sayyed, A.A.A.H.O. Tekin, R. El Mallawany, Optical properties and gamma-shielding features of bismuth borate glasses, Appl. Phys. A 124 (2018) 1–9, https://doi.org/10.1007/s00339-018-2252-7.
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Cryst. Solids 498 (2018) 443–447, https://doi.org/10.1016/j. jnoncrysol.2018.02.019. S. Barbi, C. Mugoni, M. Montorsi, M. Affatigato, C. Gatto, C. Siligardi, Structural and optical properties of rare-earths doped barium bismuth borate glasses, J. NonCryst. Solids 481 (2018) 239–247, https://doi.org/10.1016/j. jnoncrysol.2017.10.043. R. computer code Collection, MCNPX User’s Manual Version 2.4.0 Monte Carlo Particle Transport Code System for Multiple and High Energy Application, 2002. M.J. Berger, J.H. Hubbell, S.M. Seltzer, J. Chang, J.S. Coursey, R. Sukumar, D. S. Zucker, XCOM: Photon Cross Sections Database, 2010, https://doi.org/ 10.18434/T48G6X. M.R. Kaçal, F. Akman, M.I. Sayyed, Evaluation of gamma-ray and neutron attenuation properties of some polymers, Nucl. Eng. Technol. 51 (2019) 818–824, https://doi.org/10.1016/j.net.2018.11.011. M.I. Sayyed, M.G. Dong, H.O. Tekin, G. Lakshminarayana, M.A. Mahdi, Comparative investigations of gamma and neutron radiation shielding parameters
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7
for different borate and tellurite glass systems using WinXCom program and MCNPX code, Mater. Chem. Phys. 215 (2018) 183–202, https://doi.org/10.1016/j. matchemphys.2018.04.106. M.I. Sayyed, R. El Mallawany, Comparative shielding properties of some tellurite glasses: Part 1, Phys. B Phys. Condens. Matter. 539 (2017) 133–140, https://doi. org/10.1016/j.physb.2017.05.021. I.I. Bashter, A.S. Makarious, E.S. Abdo, Investigation of hematite-serpentine and ilmenite-limonite concretes for reactor radiation shielding, Ann. Nucl. Energy 23 (1996) 65–71, https://doi.org/10.1016/0306-4549(95)00011-G. P. Yasaka, N. Pattanaboonmee, H.J. Kim, P. Limkitjaroenporn, J. Kaewkhao, Gamma radiation shielding and optical properties measurements of zinc bismuth borate glasses, Ann. Nucl. Energy 68 (2014) 4–9, https://doi.org/10.1016/j. anucene.2013.12.015. http://www.schott.com/advanced_optics/english/products/optical-materials /specialmaterials/radiation-shielding-glasses/index.html.
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Physica B: Physics of Condensed Matter journal homepage: http://www.elsevier.com/locate/physb
Investigation of gamma-ray shielding capability of glasses doped with Y, Gd, Nd, Pr and Dy rare earth using MCNP-5 code K.M. Mahmoud a, b, Y.S. Rammah c, * a
Ural Federal University, St. Mira, 19, 620002, Yekaterinburg, Russia Nuclear Materials Authority, Maadi, Cairo, Egypt c Physics Department, Faculty of Science, Menoufia University, Shebin El-Koom, 32511, Menoufia, Egypt b
A R T I C L E I N F O
A B S T R A C T
Keywords: REE MAC MFP HVL Zeff Aeff
The capability of using five rare earth oxides (Y2O3 (S1-Y), Gd2O3 (S2-Gd), NdCl3 (S3-Nd), PrO11 (S4-Pr), and Dy2O3 (S5-Dy)) doped glasses as gamma-rays shielding has been evaluated. The mass attenuation coefficient (MAC, μm) in the photon energy between 0.015 and 15 MeV has been simulated with help of MCNP5- code and calculated by XCOM program. There was agreement between the calculated and simulated results. The highest μm was found for the glass samples S4-Pr, S5-Dy and S3-Nd, respectively while, the lowest μm obtained for Yttrium glass sample (S1-Y). Several another γ-rays shielding parameters such as mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and effective electron density (Aeff) for the studied glasses have been evaluated and compared with some commercial radiation shielding materials such as concretes, heavy metal oxides, and RS-520 glass. Results reveal that the lowest HVL obtained for the samples (S4-Pr and S5-Dy), while the highest HVL obtained for S1-Y sample. The highest Zeff is obtained for S4-Pr glass sample, while the lowest Zeff is obtained by S1-Y. generally, the rare earth glass samples (S4-Pr and S5-Dy) have good shielding properties corresponding to commercially standard RS-520 (SF6), Zinc bismuth borate glass (10ZnO-30Bi2O360B2O3) and concretes.
1. Introduction In our life, humans, animals, and plants can be exposed to several different types of radiations such as neutron, γ/X rays. These radiations are used in different fields like medical therapy, elemental analysis, and nuclear reactors [1]. Gamma-rays (γ-photons) characterized with no charge and mass, therefore, these photons can easily travel for very long distance in air and highly penetrate through materials. For these reasons, γ-photons are difficult to shield. In the other hand, the exposure to gamma radiation for long times may cause damage at a cellular level and are penetrating causing diffuse damage throughout the body leads to genetic damage, cancer and death. So, investigators and researchers have paid efforts to choose and develop new radiation shielding materials to protect humans from the harmful γ-photons [2–13]. To achieve this purpose, the study of radiation interaction mechanism with materials is necessary for evalu ating the level of penetration of radiation in the medium. Therefore, these knowledges have a great importance in the fields of science, in dustrial, and technology. Recently, γ-rays spectrometry techniques find
wide applications in several areas like (i) agriculture to estimate the properties of irradiation of seeds and soil samples, (ii) medical appli cations includes nuclear medicine, radiotherapy, and computerized to mography, and (iii) industry area to detect blockages in underground pipes, to control and measure the flow of liquids, and to examine defects in metal castings [14–17]. The evaluation of a radiation shielding ma terial requires accurate determination of some shielding parameters such as photon attenuation coefficient, effective atomic number, elec tron density, mean free path and half value thickness. Various materials such as alloys, polymers, concretes, glasses, ceramics, bricks, and clay materials have been considered as suitable γ-radiation shielding competence [18–23]. Nowadays, glasses have considered as promising materials for γ-photons shielding due to their high optical transparency and easy to form. Recently, Borate glasses have been prepared and investigated in wide range due to their good thermal stability, low vis cosity, high chemical resistance, low melting point, and excellent me chanical stability [6–10]. Rare earth doped glasses showed a development on the optical properties, density of the produced glasses [24–26]. Furthermore, they
* Corresponding author. E-mail address: [email protected] (Y.S. Rammah). https://doi.org/10.1016/j.physb.2019.411756 Received 16 August 2019; Received in revised form 3 October 2019; Accepted 5 October 2019 Available online 10 October 2019 0921-4526/© 2019 Elsevier B.V. All rights reserved.
Please cite this article as: K.M. Mahmoud, Y.S. Rammah, Physica B, https://doi.org/10.1016/j.physb.2019.411756
K.M. Mahmoud and Y.S. Rammah
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
22.6MgO-20.15CaO-2.52BaO-2.52ZnO-47.85SiO2-1.79B2O3-1.26A l2O3-1.26Gd2O3 (S2-Gd) [30], 65B2O3-12.5TeO2-12.5Bi2O3-5 Na2O-5NdCl3 (S3-Nd) [31], 67TeO2-20WO3-10Li2O-3PrO11 (S4-Pr) [32], and 60B2O3-20BaO-17.5Bi2O3-2.5Dy2O3 (S5-Dy) [33]. The chemical composition and density of the chosen glasses haven been listed in Table 1.
Table 1 Chemical composition and density of the selected rare earth doped glasses. Sample code
Chemical composition
Density, (g/ cm3)
Ref.
S1-Y S2-Gd
35.7Na2O-57.1B2O3-7.2Y2O3 22.6MgO-20.15CaO-2.52BaO-2.52ZnO47.85SiO2-1.79B2O3-1.26Al2O3-1.26Gd2O3 65B2O3-12.5TeO2-12.5Bi2O3-5Na2O-5NdCl3 67TeO2-20WO3-10Li2O-3PrO11 60B2O3-20BaO-17.5Bi2O3-2.5Dy2O3
2.53 3.09
[29] [30]
3.82 5.89 6.70
[31] [32] [33]
S3-Nd S4-Pr S5-Dy
2.2. Methods 2.2.1. Theoretical background Beer Lambert’s law has been used to describe the attenuation process of gamma photons as [16]:
showed a good sensitivity for absorbing UV–visible radiations and emitting visible radiations that may make it as a promising candidate for sensing electromagnetic radiations [27]. Recently, Er2O3 content found to increase the shielding properties of glass (i.e. increase of the mass attenuation coefficient μm; decrease of the half value layer HVL and exposure buildup factor EBF) [28]. In the present work, some glass systems include rare earth oxides such as Y2O3 (Yttrium oxide), Gd2O3 (Gadolinium oxide), NdCl3 (Neo dymium oxide), PrO11 (praseodymium oxide), and Dy2O3 (dysprosium oxide) have been chosen. The capability to use these systems as gamma radiation shielding has been evaluated via calculating the mass atten uation coefficient (MAC, μm) in the photon energy between 0.015 and 15 MeV. Based the values μm, several gamma-ray shielding parameters such as mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and effective electron density for the selected rare earth glasses have been evaluated and compared with some commercial shielding materials (concretes, zinc bismuth borate glass, and RS-520 glass).
I ¼ Io e
(1)
μy
Io and I represent to the intensity of the incident and transmittance photon beam, y is the absorber (the glass sample) thickness, and μ is the linear attenuation coefficient (LAC). The LAC gives the probability of photon interaction per unit length and expressed in cm 1. The mass attenuation coefficient (MAC, μm) of the absorber is calculated from μ values divided by the absorber density and expressed in cm2/g. The MAC (μ/ρ) is used to describe the γ-ray penetration and interaction with the materials and theoretically can be calculated using the mixture rule [6]. μ X �μ� MAC ¼ μm ¼ ¼ Wi (2)
ρ
i
ρ
i
2. Materials and methods
where (μ/ρ)i is the mass attenuation coefficient of the ith constituent element and wi is the weight fraction of the ith constituent element in the glass sample. The half value layer (HVL) and mean free path (MFP) for the shielding material are given by Ref. [15].
2.1. Materials
HVL ¼
The studied glass samples in the present wok have been selected from earlier reports as 35.7Na2O-57.1B2O3-7.2Y2O3 (S1-Y) [29],
MFP ¼
ln 2
(3)
μ 1
(4)
μ
The effective atomic number (Zeff) for the glass sample can be Table 2 The mass attenuation coefficient of the prepared glass samples. Energy (MeV)
Mass attenuation coefficient (cm2/g) S1-Y
0,015 0,02 0,03 0,04 0,05 0,06 0,08 0,1 0,15 0,2 0,3 0,4 0,5 0,6 0,8 1 1,5 2 3 4 5 6 8 10 15
S2-Gd
S3-Nd
S4-Pr
S5-Dy
MCNP
XCOM
MCNP
XCOM
MCNP
XCOM
MCNP
XCOM
MCNP
XCOM
3,5291 4,6686 1,9241 0,9521 0,5378 0,3819 0,2490 0,1957 0,1458 0,1260 0,1056 0,0935 0,0850 0,0784 0,0687 0,0616 0,0501 0,0432 0,0350 0,0304 0,0274 0,0254 0,0228 0,0213 0,0195
3,5400 4,9190 1,7380 0,8700 0,5374 0,3817 0,2489 0,1957 0,1460 0,1261 0,1057 0,0936 0,0851 0,0785 0,0688 0,0618 0,0503 0,0433 0,0351 0,0305 0,0275 0,0255 0,0229 0,0213 0,0195
12,4490 5,5636 1,8411 1,3729 0,8905 0,8027 0,3721 0,2640 0,1701 0,1385 0,1112 0,0972 0,0878 0,0807 0,0705 0,0631 0,0513 0,0444 0,0364 0,0320 0,0292 0,0274 0,0252 0,0240 0,0228
12,4200 5,5490 1,8380 1,3430 0,7973 0,6429 0,3709 0,2634 0,1701 0,1384 0,1112 0,0972 0,0879 0,0808 0,0706 0,0633 0,0515 0,0445 0,0365 0,0320 0,0293 0,0274 0,0252 0,0240 0,0228
21,9099 14,1212 4,9710 4,1052 3,1213 2,1522 1,0246 1,2891 0,4884 0,2777 0,1487 0,1132 0,0955 0,0846 0,0711 0,0621 0,0499 0,0433 0,0360 0,0322 0,0298 0,0284 0,0267 0,0260 0,0257
21,9200 14,1700 4,9880 4,1110 2,7230 1,7320 0,8732 1,0160 0,4269 0,2559 0,1491 0,1135 0,0957 0,0848 0,0713 0,0628 0,0503 0,0435 0,0361 0,0323 0,0299 0,0284 0,0268 0,0261 0,0257
50,5627 23,6228 8,0081 12,2029 7,8070 5,6743 3,5983 2,2196 0,7235 0,3744 0,1785 0,1217 0,0979 0,0843 0,0843 0,0587 0,0470 0,0415 0,0363 0,0343 0,0335 0,0333 0,0337 0,0346 0,0373
50,7000 23,6600 8,0850 12,9000 7,3500 4,5470 3,0920 1,7470 0,6497 0,3497 0,1747 0,1221 0,0982 0,0846 0,0690 0,0599 0,0476 0,0418 0,0366 0,0344 0,0336 0,0333 0,0337 0,0346 0,0373
32,5242 20,6714 7,2467 6,9615 4,1101 3,1452 1,5685 1,6946 0,6540 0,3586 0,1779 0,1276 0,1008 0,0876 0,0722 0,0622 0,0497 0,0432 0,0365 0,0332 0,0313 0,0301 0,0291 0,0288 0,0294
32,5400 20,7400 7,2650 7,0660 4,0060 2,7120 1,3290 1,4590 0,5767 0,3245 0,1718 0,1237 0,1011 0,0879 0,0724 0,0631 0,0501 0,0435 0,0367 0,0333 0,0314 0,0302 0,0291 0,0289 0,0294
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Physica B: Physics of Condensed Matter xxx (xxxx) xxx
Fig. 1. The variation of the mass attenuation coefficient with the incident gamma ray energy for [A] Yttrium glass, [B] Gadolinium glass, [C] Neodymium glass, [D] presidium glass and [E] Dysprosium glass.
Fig. 2. The variation of MFP of the prepared concrete with the incident gamma ray energy.
calculated using the following relations �� P μ i fi Ai ρ Zeff ¼ P � � i Aj μ j Zj
ρ
Fig. 3. The Variation of HVL with the incident gamma ray energy.
Where NA is Avogardo’s number and M is the atomic mass of the glass. 2.2.2. MNCP-5 simulation code In the currently work, the μ/ρ has been simulated for the chosen glasses using Monte Carlo N particle transport code MCNP- 5 code [34]. This code used to model the interaction of neutrons, gamma-rays, X-rays, and electrons with different materials. In the simulation pro cess, MCNP- 5 code needs an input file includes all data about elemental composition, density, and geometry specification of the proposed ma terial, source specification and tally, more description in Ref. [23].
(5)
j
Where fi Ai and Zj refers to the fractional abundance, atomic weight and atomic number of the ith constituent element respectively. Additionally, the effective electron density (Neff) can be estimated using (Zeff) as: Aeff ¼
X NA ni Zeff M
2.2.3. XCOM program XCOM is a database has been established by Berger and Hubell in
(6)
3
K.M. Mahmoud and Y.S. Rammah
Physica B: Physics of Condensed Matter xxx (xxxx) xxx
Fig. 6. Comparison between the μm of studied samples and some available radiation shielding.
Fig. 4. The variation of the Zeff with the incident energy between 0.01 and 15 MeV.
Fig. 7. Comparison between the HVL of studied samples and some available radiation shielding.
Fig. 5. The variation of the Aeff with the incident energy between 0.01 and 15 MeV.
tends to its maximum value 3.529 cm2/g at low gamma ray energy (for 0.015 MeV) then, it decreases rapidly with the incident energy increase between (0.015 < E < 0.08 MeV) due to the photoelectric cross section which proportional to E 3.5 and Z4 5 [15]. Fig. 1A shows a sudden peak at energy 0.017 MeV due to the K absorption edges of Yttrium. No peaks appear due to Na element because it is occurring only at 0.00107 MeV while we selected the energy range to start from 0.015 MeV. Further increase of the incident gamma ray energy leads to a gradually decrease in the μm between (0.08 < E < 3 MeV) due to the Compton scattering cross section with proportional to the shielding material atomic number [37]. The μm has a slow variation with the incident energy for high incident energy (E > 3 MeV) due to the pair production cross section which proportional to log E [23]. The μm tends to its minimum values 0.0194 cm2/g at high gamma ray energy (for 15 MeV). Fig. 1B reveals that the μm for Gadolinium glass samples (S2-Gd) tends to maximum value 12.449 cm2/g at gamma ray energy 0.015 MeV while the μm tends to minimum values 0.0227 cm2/g at 15 MeV. Fig. 1B illustrates that there are two suddenly peaks at low energy, the first appears at 0.0374 MeV due to K absorption edges of Ba while, the second
1987 to calculate the mass attenuation coefficient of compounds, ele ments, and mixtures in energy range between (1 KeV < E < 1 GeV) [35]. Several researchers have been used the XCOM database to calculate the mass attenuation coefficient for different materials such as polymers, concretes, building materials and glasses [1,10,23,36]. 3. Results and discussion The mass attenuation coefficient μm simulated for five different glass samples prepared with additive of some rare earth elements (Y, Gd, Nd, Pr and Dy) using MCNP-5 code. Furthermore, the μm calculated theo retically for the prepared samples using XCOM data base between 0.015 and 15 MeV as listed in Table 2. It is clear that from Fig. 1 the μm for all prepared glass samples depended on the incident gamma ray energy and the additive materials. Also Fig. 1 reveals that the simulated and calculated are closed together which insure the accuracy of simulation processes. It is clear that from Fig. 1A, the μm of Yttrium glass samples (S1 -Y) 4
K.M. Mahmoud and Y.S. Rammah
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Table 3 Comparison between the values of the half value layers of the prepared glass samples and other known shielding materials. Energy (MeV) 0,015 0,02 0,03 0,04 0,05 0,06 0,08 0,1 0,15 0,2 0,3 0,4 0,5 0,6 0,8 1 1,5 2 3 4 5 6 8 10 15
Half value layer (cm) S1-Y
S2-Gd
S3-Nd
S4-Pr
S5-Dy
Concrete
Zinc Bismuth borate glass
RS-520 (SF6)
0,078 0,059 0,142 0,288 0,509 0,717 1,100 1,400 1,879 2,174 2,596 2,929 3,223 3,494 3,985 4,446 5,464 6,342 7,821 9,012 9,989 10,798 12,018 12,869 14,082
0,018 0,040 0,122 0,163 0,252 0,279 0,603 0,850 1,318 1,620 2,018 2,308 2,555 2,779 3,180 3,557 4,369 5,055 6,168 7,017 7,679 8,197 8,915 9,358 9,860
0,008 0,012 0,034 0,041 0,054 0,078 0,165 0,131 0,345 0,607 1,134 1,490 1,766 1,994 2,371 2,716 3,379 3,897 4,686 5,246 5,651 5,947 6,310 6,489 6,575
0,002 0,005 0,015 0,010 0,015 0,021 0,033 0,053 0,163 0,314 0,659 0,967 1,202 1,396 1,396 2,005 2,504 2,838 3,238 3,430 3,513 3,539 3,496 3,404 3,156
0,003 0,005 0,014 0,015 0,025 0,033 0,066 0,061 0,158 0,289 0,581 0,811 1,026 1,181 1,433 1,663 2,083 2,393 2,834 3,121 3,310 3,435 3,560 3,592 3,524
0,043 0,097 0,288 0,556 0,841 1,247 1,475 1,747 2,111 2,371 2,774 3,114 3,418 3,770 4,218 4,693 5,764 6,685 8,214 9,430 10,411 11,201 12,369 13,152 14,199
0,004 0,006 0,018 0,039 0,070 0,112 0,224 0,105 0,267 0,482 0,938 1,325 1,635 1,889 2,304 2,648 3,334 3,835 4,550 5,022 5,335 5,544 5,759 5,822 5,726
0,002 0,003 0,008 0,017 0,031 0,050 0,044 0,118 0,231 0,522 0,825 1,094 1,329 1,712 2,026 2,610 2,972 2,996 3,382 3,577 3,658 3,675 3,622 3,520 3,248
appears at 0.0502 MeV due to Gadolinium K-absorption edges. No peaks are found from Al, Si, Ca and Zn elements. Fig. 1C depicts that the highest μm for Neodymium glass samples (S3-Nd) is 21.909 cm2/g and observed at low energy 0.015 MeV while, the lowest μm is 0.0256 cm2/g and observed at 15 MeV. It is clear that there are 3 different peaks in the low gamma ray energy. The peaks appear at 0.0318,0.0436 and 0.0905 due the K-absorption edges of Te, Nd and Bi, respectively. The μm for S3Nd glass tends to minimum value 0.0265 cm2/g at 15 MeV wile, no peaks appear from chlorine. The results illustrated in Fig. 1D, show that the μm of the praseo dymium glass (S4-Pr) tends to a maximum value 50.562 cm2/g at 0.015 MeV, while it tends to a minimum value 0.0373 cm2/g at 15 MeV. Two different peaks appear at 0.0420 and 0.0695 MeV due to the K absorption edges of praseodymium and tungsten, respectively. Fig. 1E reveals that the highest μm for dysprosium glass (S5-Dy) is 32.524 cm2/g and obtained for 0.015 MeV, while the lowest μm is 0.0197 cm2/g and obtained for 15 MeV. It is clear that three different peaks appear at 0.0374, 0.0538 and 0.0905 MeV due to the K absorption edges of Ba, Dy and Bi, respectively [38]. In the present work and according to the previous discussion, it is clear that the highest three μm obtained for S4-Pr, S5-Dy and S3-Nd, respectively, while the lowest μm obtained for Yttrium glass sample (S1-Y). Furthermore, the simulated μm used to calculate other important shielding parameters such as MFP, HVL, Zeff and Aeff that describe the penetration, diffusion, and interaction of the incident gamma ray inside the shielding material. Fig. 2 depicts the variation of the MFP of all prepared glass samples with the incident gamma ray energy between 0.015 and 15 MeV. It is clear that for all REE/glass samples the MFP tends to its minimum values at low energy (for 0.015 MeV) and varied between 0.00335 and 0.112 cm for (S4-Pr and S5-Dy) and S1-Y, respectively. Then, further increases in the incident energy the MFP increase rapidly due to the photoelectric cross section which propor tional to E 3.5. In the intermediate energy range (for 0.1 < E < 3 MeV), the MFP increases gradually with increase the incident energy due to the Compton scattering cross section which depended only atomic number of the shielding material, while there are a slow variation in the MFP for the prepared REE/glass samples at high energy (E > 3 MeV) due to the pair production cross section which proportional to log E. The MFP tends
to maximum values at high energy (for 15 MeV) and it is varied between 4.553 and 20.316 cm for S4-Pr and S1-Y, respectively. The lowest MFP is obtained for samples (S4-Pr and S5-Dy) and varied between 0.00335 and 4.553 cm, while the highest MFP obtained for S1-Y sample and varied between 0.112 and 20.316 in energy range between 0.015 and 15 MeV. Fig. 3 reveals that the dependence of the HVL of the prepared REE/ glass on the incident gamma ray energy which can be described as in the previous section of the MFP. The lowest HVL obtained for the samples (S4-Pr and S5-Dy) and varied between 0.00232 and 3.156 cm at gamma ray energy between 0.015 MeV and 15 MeV. The highest HVL obtained for S1-Y sample and varied between 0.0776 and 14.081 cm. The previous discussion of the μm, HVL and MFP reveals that the glass samples with Pr and Dy (S4-Pr and S5-Dy) have the best shielding parameters, while the sample S1-Y has the lowest shielding properties in the present study. Fig. 4 depicts that the variation of the Zeff of the prepared REE/glass with the incident gamma ray energy between 0.01 and 15 MeV. It is observed that the Zeff for all glass samples tends to maximum values at low energy between 0.02 and 0.04 MeV, while it tends to minimum values at intermediate energy between 1.332 and 1.5 MeV. Fig. 4 reveals that in energy region between 0.01 and 0.3 MeV, the Zeff for all glass samples decreases rapidly with increase of the incident gamma ray en ergy due to the photoelectric cross section. It is also observed that there a suddenly increase in the Zeff at low energy due to the K absorption edges of Y, Gd, Nd, Pr and Dy. Further increases in the incident gamma ray energy, the Zeff decreases gradually due to the Compton scattering cross section. It is also clear that for high energy region (E > 3 MeV), the Zeff increases slowly with the increase of the incident energy due to the pair production cross section. The highest Zeff is obtained for S4-Pr glass sample and varied between 45.610 and 61.634 while, the lowest Zeff is obtained by S1-Y and varied between 10.067 and 33.290. Fig. 5 reveals that the dependence of the Aeff on the incident gamma ray energy. It is clear that, the variation of Aeff with the incident gamma ray energy can be discussed as in the Zeff section. The highest Aeff is obtained for S1-Y and varied between 2.977 � 1023 and 9.85 � 1023 electrons/g while the lowest Aeff is obtained for S4-Pr and varied be tween 2.741 � 1023 and 3.704 � 1023 electrons/g. Fig. 6 reveals that a comparison between the μm for the highest three glass samples in this work (S4-Pr, S5- Dy and S3-Nd) and the μm for some 5
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K.M. Mahmoud and Y.S. Rammah
available radiation shielding materials such as concrete [39], Zinc bis muth borate glass oxides (10ZnO-30Bi2O3-60B2O3) [40], and Rs-520 (SF6) glass [41]. Fig. 6 displays that, the μm for S4-Pr and S5-Dy higher than the μm for the ordinary concrete and heavy metal oxides but lower than the μm for glass Rs-520 while, glass sample S3-Nd has μm higher than ordinary concrete but lower than the Zinc bismuth borate glass. Fig. 7 and Table 3 showed the comparison between the HVL of our prepared samples and those for some radiation shielding materials. The HVL of our sample S4-Pr equal to the HVL for RS-520 glass while it is higher than the HVL of ordinary concrete and zinc bismuth borate glass. It is also clear that the S5-Dy sample has HVL lower than RS-520, or dinary concrete and heavy metal oxides. Finally, we can conclude that our REE/glass samples (S4-Pr and S5Dy) have good shielding properties corresponding to commercially standard RS-520 (SF6) and available radiation shielding materials namely zinc bismuth borate glass (10ZnO-30Bi2O3-60B2O3) and concretes.
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4. Conclusion This work aimed to evaluate the capability of using five rare earth oxides (Y2O3, Gd2O3, NdCl3, PrO11, and Dy2O3) doped glasses as gamma radiation shielding. The mass attenuation coefficient (MAC, μm) in the photon energy between 0.015 and 15 MeV has been simulated using MCNP5- code and calculated by XCOM program. The comparison showed agreement between the calculated and simulated results. Based the μm values, many gamma-rays shielding parameters such as mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and effective electron density for the glasses have been evaluated and compared with some commercial radiation shielding materials such as concretes, zinc bismuth borate glass, and RS-520 glass. Results reveal that: 1 The highest μm was obtained for glass samples S4-Pr, S5-Dy and S3Nd, respectively while, the lowest μm obtained for Yttrium glass sample (S1-Y). 2 The lowest HVL obtained for the samples (S4-Pr and S5-Dy) and varied between 0.00232 and 3.156 cm at gamma ray energy between 0.015 MeV and 15 MeV. The highest HVL obtained for S1-Y sample and varied between 0.0776 and 14.081 cm. 3 The highest Zeff is obtained for S4-Pr glass sample and varied be tween 45.610 and 61.634 while, the lowest Zeff is obtained by S1-Y and varied between 10.067 and 33.290. Finally, one can conclude that our REE/glass samples (S4-Pr and S5Dy) have good shielding properties corresponding to commercially standard RS-520 (SF6), available zinc bismuth borate glass (10ZnO30Bi2O3-60B2O3) and concretes. References [1] K.A. Mahmoud, O.L. Tashlykov, A.F. El Wakil, I.E. El Aassy, Aggregates grain size and press rate dependence of the shielding parameters for some concretes, Prog. Nucl. Energy 118 (2020), 103092, https://doi.org/10.1016/j. pnucene.2019.103092. [2] M.I. Sayyed, K.M. Kaky, D.K. Gaikwad, O. Agar, U.P. Gawai, S.O. Baki, Physical, structural, optical and gamma radiation shielding properties of borate glasses containing heavy metals (Bi2O3/MoO3, J. Non-Cryst. Solids 507 (2019) 30–37. [3] Y.S. Rammah, M.I. Sayyed, A.S. Abohaswa, H.O. Tekin, FTIR, electronic polarizability and shielding parameters of B2O3 glasses doped with SnO2, Appl. Phys. A 124 (2018) 650. [4] A.M.A. Mostafa, S.A.M. Issa, M.I. Sayyed, Gamma ray shielding properties of PbOB2O3 -P2O5 doped with WO3, J. Alloy. Comp. 708 (2017) 294–300. [5] M.I. Sayyed, M.H.M. Zaid, K.A. Matori, Comprehensive study on physical, elastic and shielding properties of ternary BaO-Bi2O3-P2O5 glasses as a potent radiation shielding material, J. Non-Cryst. Solids 468 (2017) 92–99, https://doi.org/ 10.1016/j.jnoncrysol.2017.04.031. [6] Y.S. Rammah, M.I. Sayyed, A.A.A.H.O. Tekin, R. El Mallawany, Optical properties and gamma-shielding features of bismuth borate glasses, Appl. Phys. A 124 (2018) 1–9, https://doi.org/10.1007/s00339-018-2252-7.
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